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Burnup Dependent Uo2 Thermal Conductivity Degradation And Its Impact On Candu Fuel As Extended Burnup
Download Burnup Dependent Uo2 Thermal Conductivity Degradation And Its Impact On Candu Fuel As Extended Burnup full books in PDF, epub, and Kindle. Read online Burnup Dependent Uo2 Thermal Conductivity Degradation And Its Impact On Candu Fuel As Extended Burnup ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!
Book Synopsis Burnup-dependent uo2 thermal conductivity degradation and its impact on CANDU fuel as extended burnup by : V. I. Arimescu
Download or read book Burnup-dependent uo2 thermal conductivity degradation and its impact on CANDU fuel as extended burnup written by V. I. Arimescu and published by . This book was released on 1993 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: This document consists of candu zr-2.5nb pressure tube inspection and operating data primarily for ontario hydro reactors. the data presented here represent the current contents of the in-reactor deformation database developed and maintained at ohrd/1/. it is intended for use in the understanding of the deformation behaviour of fuel channels in power reactors and in the derivation and fine-tuning of material creep and growth constants for the new deformation equations. in compiling and presenting the deformation and operating data of fuel channels the databse provides a statistical sample of the actual operating behaviour of components in candu power reactors. this sample may be used to detect any abnormal or unexpected effects and to provide a means of comparison between different power reactos. with the future addition of 600 mw and experimental reactor data, this information will play a key role in the development of a broader understanding of fuel channel behaviour in the ongoing process of extending the operating lives of candu reactors. this document represents the first issue of the information in the database in a 3-ring binder format. it is felt that this format will avoid the need to re-issue the entire document when new information becomes available. it will be the responsibility of ohrd to provide updates on a regular basis (most likely annually). the information is divided into three sections: the first section contains diametral expansion inspection data for individual fuel channels, the second contains the sag inspection data, and the third contains the reactor operating data. within each section are three subsections: a legend describing the tables, information on the source and processing of the data in the tables, and the tables of the data.
Book Synopsis Summary Report on UO2 Thermal Conductivity Model Refinement and Assessment Studies by :
Download or read book Summary Report on UO2 Thermal Conductivity Model Refinement and Assessment Studies written by and published by . This book was released on 2017 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt: Uranium dioxide (UO2) is the most commonly used fuel in light water nuclear reactors and thermal conductivity controls the removal of heat produced by fission, therefore, governing fuel temperature during normal and accident conditions. The use of fuel performance codes by the industry to predict operational behavior is widespread. A primary source of uncertainty in these codes is thermal conductivity, and optimized fuel utilization may be possible if existing empirical models were replaced with models that incorporate explicit thermal conductivity degradation mechanisms during fuel burn-up. This approach is able to represent the degradation of thermal conductivity due to each individual defect type, rather than the overall burn-up measure typically used which is not an accurate representation of the chemical or microstructure state of the fuel that actually governs thermal conductivity and other properties. To generate a mechanistic thermal conductivity model, molecular dynamics (MD) simulations of UO2 thermal conductivity including representative uranium and oxygen defects and fission products are carried out. These calculations employ a standard Buckingham type interatomic potential and a potential that combines the many-body embedded atom method potential with Morse-Buckingham pair potentials. Potential parameters for UO2+x and ZrO2 are developed for the latter potential. Physical insights from the resonant phonon-spin scattering mechanism due to spins on the magnetic uranium ions have been introduced into the treatment of the MD results, with the corresponding relaxation time derived from existing experimental data. High defect scattering is predicted for Xe atoms compared to that of La and Zr ions. Uranium defects reduce the thermal conductivity more than oxygen defects. For each defect and fission product, scattering parameters are derived for application in both a Callaway model and the corresponding high-temperature model typically used in fuel performance codes. The model is validated by comparison to low-temperature experimental measurements on single crystal hyper-stoichiometric UO2+x samples and high-temperature literature data. Ongoing works include investigation of the effect of phase separation to UO2+U4O9 on the low temperature thermal conductivity of UO2+x, and modeling of thermal conductivity using the Green-Kubo method. Ultimately, this work will enable more accurate fuel performance simulations as well as extension to new fuel types and operating conditions, all of which improve the fuel economics of nuclear energy and maintain high fuel reliability and safety.
Book Synopsis Irradiation and Examination of Vibratory Packed UO2 High Burnup Program Fuel Elements by : T. J. Slosek
Download or read book Irradiation and Examination of Vibratory Packed UO2 High Burnup Program Fuel Elements written by T. J. Slosek and published by . This book was released on 1960 with total page 78 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Analysis of Burnup Effect on Thermal Conductivity of UO2 During Irradiation by : Chern Hwa Tsai
Download or read book Analysis of Burnup Effect on Thermal Conductivity of UO2 During Irradiation written by Chern Hwa Tsai and published by . This book was released on 1971 with total page 166 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis 4th International Conference on CANDU Fuel by :
Download or read book 4th International Conference on CANDU Fuel written by and published by . This book was released on 1995 with total page 516 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :Arimescu, V. I Publisher :Chalk River, Ont. : Fuel Engineering Branch, Chalk River Laboratories ISBN 13 : Total Pages :15 pages Book Rating :4.:/5 (327 download)
Book Synopsis Extended-burnup CANDU Fuel : Description of Database and Comparisons with Code Predictions by : Arimescu, V. I
Download or read book Extended-burnup CANDU Fuel : Description of Database and Comparisons with Code Predictions written by Arimescu, V. I and published by Chalk River, Ont. : Fuel Engineering Branch, Chalk River Laboratories. This book was released on 1992 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Extended-burnup CANDU Fuel by : Chalk River Nuclear Laboratories
Download or read book Extended-burnup CANDU Fuel written by Chalk River Nuclear Laboratories and published by . This book was released on 1992 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: Interest in the modelling of extended-burnup CANDU fuel has been prompted by the examination of such fuel from CANDU reactors and the development of extended-burnup CANDU fuel for the future. A study was done to compile a database on experimental irradiations whose outer-element burnups exceed 300 MWh/kgU. This paper describes the elements that comprise the database and discusses analysis of fission-gas-release measurement against experimental parameters. Fission-gas-release measurements are also compared against predicted results from the MOD10 and MOD11 versions of the code ELESIM.
Download or read book Technical Reports Series written by and published by . This book was released on 2002 with total page 1402 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Improvement of Computer Codes Used for Fuel Behaviour Simulation (Fumex-III) by : International Atomic Energy Agency
Download or read book Improvement of Computer Codes Used for Fuel Behaviour Simulation (Fumex-III) written by International Atomic Energy Agency and published by IAEA Tecdoc. This book was released on 2013 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: The modelling of the performance of nuclear fuel is crucial to the operation of nuclear power plants and comprises a key component of the demonstration of nuclear safety. As the demands on fuel performance increase, fuel modelling codes need to develop and cover a wider range of operational and transient conditions. This publication compares the predictions of current fuel modelling codes with data representing a wide range of fuel operational conditions. The results demonstrate both excellent performance and areas for further development of the codes to support advanced fuel operations.
Author :Arimescu, V. I Publisher :Chalk River, Ont. : Fuel Engineering Branch, Chalk River Laboratories ISBN 13 : Total Pages :22 pages Book Rating :4.:/5 (268 download)
Book Synopsis Modeling CANDU-type Fuel Behaviour During Extended Burnup Irradiations Using a Revised Version of the ELESIM Code by : Arimescu, V. I
Download or read book Modeling CANDU-type Fuel Behaviour During Extended Burnup Irradiations Using a Revised Version of the ELESIM Code written by Arimescu, V. I and published by Chalk River, Ont. : Fuel Engineering Branch, Chalk River Laboratories. This book was released on 1992 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Research Abstracts written by and published by . This book was released on 1993 with total page 354 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Heavy Water Reactors by : International Atomic Energy Agency
Download or read book Heavy Water Reactors written by International Atomic Energy Agency and published by . This book was released on 2002 with total page 728 pages. Available in PDF, EPUB and Kindle. Book excerpt: Outlines the characteristics of heavy water reactors and provides an insight into the technology for specialists in countries where the establishment of nuclear power programmes is being considered. This report should serve as a reference for engineers and scientists working in the field, as well as for lecturers in nuclear technology.
Book Synopsis A Review of the Effects of Burnup on the Thermal Conductivity of UO2 by : Ryan O. Lokken
Download or read book A Review of the Effects of Burnup on the Thermal Conductivity of UO2 written by Ryan O. Lokken and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor by : Willem Frederik Geert van Rooijen
Download or read book Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor written by Willem Frederik Geert van Rooijen and published by IOS Press. This book was released on 2006 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Generation IV Forum is an international nuclear energy research initiative aimed at developing the fourth generation of nuclear reactors, envisaged to enter service halfway the 21st century. One of the Generation IV reactor systems is the Gas Cooled Fast Reactor (GCFR), the subject of study in this thesis. The Generation IV reactor concepts should improve all aspects of nuclear power generation. Within Generation IV, the GCFR concept specifically targets sustainability of nuclear power generation. The Gas Cooled Fast Reactor core power density is high in comparison to other gas cooled reactor concepts. Like all nuclear reactors, the GCFR produces decay heat after shut down, which has to be transported out of the reactor under all circumstances. The layout of the primary system therefore focuses on using natural convection Decay Heat Removal (DHR) where possible, with a large coolant fraction in the core to reduce friction losses.
Book Synopsis Review of Fuel Failures in Water Cooled Reactors (2006-2015): IAEA Nuclear Energy Series No. Nf-T-2.5 by : International Atomic Energy Agency
Download or read book Review of Fuel Failures in Water Cooled Reactors (2006-2015): IAEA Nuclear Energy Series No. Nf-T-2.5 written by International Atomic Energy Agency and published by . This book was released on 2019-12-19 with total page 65 pages. Available in PDF, EPUB and Kindle. Book excerpt: This updated version of Nuclear Energy Series NF-T-2.1 provides information on all aspects of fuel failures in current nuclear power plant operations.
Book Synopsis Proceedings of the Seminar on Thermal Performance of High Burn-up LWR Fuel by :
Download or read book Proceedings of the Seminar on Thermal Performance of High Burn-up LWR Fuel written by and published by . This book was released on 1998 with total page 400 pages. Available in PDF, EPUB and Kindle. Book excerpt: LWR = Light water reactor. On title page: OECD proceedings. On cover: Nuclear science
Book Synopsis Handbook of Nuclear Engineering by : Dan Gabriel Cacuci
Download or read book Handbook of Nuclear Engineering written by Dan Gabriel Cacuci and published by Springer Science & Business Media. This book was released on 2010-09-14 with total page 3701 pages. Available in PDF, EPUB and Kindle. Book excerpt: This is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering. Addressing nuclear engineers and scientists at all levels, this book provides a condensed reference on nuclear engineering since 1958.
